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論文

Scaling issues for the experimental characterization of reactor coolant system in integral test facilities and role of system code as extrapolation tool

Mascari, F.*; 中村 秀夫; Umminger, K.*; De Rosa, F.*; D'auria, F.*

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.4921 - 4934, 2015/08

The phenomenological analyses and thermal hydraulic characterization of a nuclear reactor are the basis for its design and safety evaluation. Scaled down tests of Integral Effect Test (IET) and Separate Effect Test (SET) are feasible to develop database. Though several scaling methods such as Power/Volume, Three level scaling and H2TS have been developed and applied to the IET and SET design, direct extrapolation of the data to prototype is in general difficult due to unavoidable scaling distortions. Constraints in construction and funding for test facility demand that a scaling compromise is inevitable further. Scaling approaches such as preservation of time, pressure and power etc. have to be adopted in the facility design. This paper analyzes some IET scaling approaches, starting from a brief analysis of the main characteristics of IETs and SETFs. Scaling approaches and their constraints in ROSA-III, FIST and PIPER-ONE facility are used to analyze their impact to the experimental prediction in Small Break LOCA counterpart tests. The liquid level behavior in the core are discussed for facility scaling-up limits.

論文

Scattering of $$^{11}$$Be halo nucleus from $$^{209}$$Bi at coulomb barrier

Mazzocco, M.*; Signorini, C.*; Romoli, M.*; De Francesco, A.*; Di Pietro, M.*; Vardaci, E.*; 吉田 光一*; 吉田 敦*; Bonetti, R.*; De Rosa, A.*; et al.

European Physical Journal A, 28(3), p.295 - 299, 2006/06

 被引用回数:42 パーセンタイル:90.01(Physics, Nuclear)

弱く束縛されたハロー核 $$^{11}$$Beの$$^{209}$$Bによる散乱を40MeVで測定した。低強度・低エミッタンスの放射性ビームによる実験であったが、8個のSiテレスコープからなる大立体角($$sim$$2$$pi$$ sr)かつコンパクトな検出器により測定が可能となった。$$^{9,11}$$Beの散乱角度分布と相対的な核反応断面積は、似たような振る舞いであることがわかった。このことは、クーロン障壁近傍におけるハロー構造あるいは弱く束縛された系の反応機構に与える影響は余り大きくないことを示唆するものである。

口頭

Scaling rationale design and extrapolation problem for ITF and SETF

Mascari, F.*; 中村 秀夫; De Rosa, F.*; D'auria, F.*

no journal, , 

In the development and safety evaluation of LWRs, thermal hydraulic analysis of the reactor, containment and their coupling is essential to understand the accident phenomena. To reproduce the behavior in a scaled model, it is necessary to properly characterize thermal hydraulics both in the local and integral responses. The facility geometry and test conditions should then be correctly derived according to scaling laws to avoid scaling distortions that could compromise the target phenomena identified by PIRT process. Many scaling approach and methods have thus been developed. Together with the scaling analysis, computer codes may be used in supporting the design of test facilities, assessing the scale distortions, and verifying the selected scaling method. However, since the closure laws in the computer code are mainly based on scaled test data, the extrapolation of code results remains a challenging and open issue. This paper provides some insights about the methods used in the scaling.

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